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Investigation of the electric field structure in neutral-beam-heated ISX-B plasmas

Thesis/Dissertation ·
OSTI ID:5086839
Plasma potentials were measured for the first time in neutral beam heated tokamak discharges. Radial potential profiles were obtained for coinjection, counterinjection, and balanced injection discharges as well as for ohmically heated plasmas in the Impurity Study Experiment (ISX-B) tokamak. Within experimental uncertainties, the measured values of potential are consistent with calculations based on radial momentum balance using experimental values of rotation velocities, density, and ion temperature. The measurements were made using a heavy ion beam probe, with typical plasma conditions of I/sub p/ approx. = 150 kA, B/sub T/ approx. = 12.3 kG, n/sub e/ approx. = 4 x 10/sup 13/ cm/sup -3/, and P/sub b/ approx. = 0.9 MW. A negative potential well depth of about 1.0 kV was observed in ohmically heated plasmas and increased somewhat for balanced injection. Counterinjection resulted in a significantly larger well depth approximately 3-4 kV, while coinjection showed an outward pointing electric field in the plasma interior. In ohmically heated plasmas the potential was constant in time, but significant time variations in potential were observed in neutral beam heated discharges. Potentials in ohmic plasmas showed both a density and a plasma current dependence. There was an observed improvement in the particle confinement times of both ions and impurities with counterinjection as compared with coinjection.
Research Organization:
Rensselaer Polytechnic Inst., Troy, NY (USA)
OSTI ID:
5086839
Country of Publication:
United States
Language:
English